ML17056A871
| ML17056A871 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point |
| Issue date: | 05/30/1990 |
| From: | Conte R, Pullani S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17056A870 | List: |
| References | |
| 50-410-90-16OL, NUDOCS 9006060044 | |
| Download: ML17056A871 (84) | |
See also: IR 05000410/1990016
Text
NY 3i l990
U.
S.
NUCLEAR REGULATORY COMMISSION
REGION I
Combined Report
No
~
Facility Docket No.:
Facility License
No.
Licensee:
Facility:
Examination Dates:
NRC Examiners:
Chief Examiner:
90-16
(OL)
50-410
Niagara
Mohawk Power Corporation
301 Plainfield Road
Syracuse,
13212
Nine Mile Point Nuclear Station,
Unit 2
April 30 - May 4,
1990
S. Pullani, Senior Operations
Engineer
J . Williams, Senior Operations
Engineer
PE Bonnett, Operations
Engineer
G. Buckley, Examiner,
PNL
L. Larson
aminer,
PNL
S. Pullani,
Operations
Engineer
Date
Approved By:
ichard
.
onte, Chief,
BWR Section
Operations
Branch,
Summary:
See
Executive
Summary
5 m po
ate
EXECUTIVE SUMMARY
Written and operating
examinations
were administered
to three
crews c'onsisting
of nine Reactor Operators
(ROs)
and six Senior Reactor Operators
(SROs).
The
examinations
were graded concurrently
by the
NRC and the facility training
staff.
The results of the
NRC and the facility grading were identical.
All of
the
ROs and all of the
examined
passed all portions of the examination.
All three
crews that were evaluated
performed satisfactorily
on the simulator
portion of the examinations.
During this examination
process,
the
NRC team also
reviewed the implementation
of Niagara
Mohawk's corrective actions to address
the deficiencies identified
during the July
1989 requalification examination
which resulted
in an unsatis-
factory requalification
program evaluation.
These corrective actions
are
documented
in the Requalification
Program Action Plan attached
to Niagara
Mohawk's letter dated January
10,
1990.
The team concluded that the corrective
actions
were essentially
complete
and generally effective
and that
a signifi-
cant
improvement in the requalification program was evident.
To return the
program to
a satisfactory
status,
Niagara
Mohawk must complete all short term
corrective actions
and certify that all program deficiencies
have
been
addressed.
The examination
team also
made
an assessment
regarding
Niagara
Mohawk's Restart
Action Plan
(RAP) Underlying Root Causes
2 (Problem Solving) and
4 (Standards
of Performance/Self-Assessment.
A significant improvement in these
areas
was
noted.
This report (Section
9) also documents
a violation identified by Niagara
Mohawk
in its letter dated
February
21,
1990,
involving medical
examinations
of
licensed operators.
In reviewing this matter,
the
NRC staff has determined
that issuing
a Notice of Violation is not appropriate.
The staff has
chosen
to
exercise this discretion
because
the violation meets all of the criteria of
Appendix
C of 10 CFR Part 2, Section
G, for a licensee identified violation.
DETAILS
1.
Introducti on
During the examination period,
the
NRC administered requalification exami-
nations
to
15 licensed operators
(9
and
6 SROs).
Ten of the
15 oper-
ators belong to two regular plant operating shifts crews (five per shift)
and the remaining five belong to one licensed staff crew.
The
15 oper-
ators were divided into 3 crews for the simulator part of the examination.
The examiners
used
the process
and criteria described
in
"Operator Licensing Examiner Standards,"
Revision 5, section
"Administration of NRC Requalification
Program Evaluations."
The exami-
ners also reviewed the licensee's
procedures
for conducting
licensed
operator
training and the results of the requalification examinations
administered
by the facility.
An entrance
meeting
was held with the licensee
on April 9,
1990, at the
site.
The purpose of this meeting
was to brief the licensee
on the
requi rements of the requalification
program evaluation
and to outline
a
prospective
schedule
for the examination.
The licensee
personnel
contacted
during the examination
are listed in Attachment
1.
The members
of the combined NRC/facility examination
team,
and the facility evaluator s
are also identified in Attachment
1.
2.
Examination Results
2. 1
Individual Examination Results
The following is
a
summary of the individual examination results:
TOTAL
NRC Grading
Written
Simulator
Walk-Through
Overall
9/0
9/0
9/0
9/0
6/0
6/0
6/0
6/0
15/0
15/0
15/0
15/0
Pass/Fail
Pass/Fail
Pass/Fail
TOTAL
Facility Grading
Written
Simulator
Walk-Through
Overall
9/0
9/0
9/0
9/0
6/0
6/0
6/0
6/0
15/0
15/0
15/0
15/0
Pass/Fail
Pass/Fail
Pass/Fail
2.2
Generic Stren ths and Weaknesses
The following is
a
summary of generic strengths
and weaknesses
noted
by the
NRC from the preparation,
administration,,and
grading of the
requalification examinations.
This information is being provided to
aid the licensee
in upgrading the requalification training program.
No licensee
response
is required.
2.2.1
0 erator Stren ths
and Weaknesses
~Siren ths:
~
Teamwork
among the crews
has
improved.
A chain-of-command,
accountability,
and improved communications
has
helped
organize
and co-ordinate
crew actions.
~
Communication skills have
improved since the previous
examination.
Formal repeat
backs,
acknowledgement
of
reports/directions
and
use of precise
language
resulted
in
a professional
atmosphere
in the control
room.
~
Station Shift Supervisor (SSS)/Assistant
Station Shift
Supervisor
(ASSS) direction and control of the shift
provided the operators
a sense of priority and account-
ability for their responsibilities
and those of the other
operators.
~
The crew'
ability to identify and evaluate
plant condi-
tions enabled
them to mitigate the effects of the event or
failure on the plant.
This included timely response
to
alarms
and awareness
of changing plant parameters
that
occurred prior to the alarm annunciating.
~
The operators
used
procedures
when appropriate,
and went
back to check the procedure if a task was performed without
a procedure
in hand.
~
The operators
displayed
a detailed
knowledge of the control
room panels.
~
Overall,
performance
of the Job Performance
Measures
(JPMs),
both in plant and simulator,
was considered
a
strength.
Weaknesses:
~
Although- communication skills have
improved, there are
still a few weaknesses,
The operators
did not always
speak
loudly enough to ensure all operators
in the control
room
were aware of changes
occurring in the plant.
During
emergencies,
all of the operators
were not always kept
abreast
of trends
and changes
in plant parameters
concern-
ing the reactor
and containment.
~
The
SSS/ASSS
did not always ensure that the entire crew was
aware of equipment that was declared
when the
classification of an emergency
event
had occurred
and the
reason for it; and when reentry into the
had taken
place.
~
Ouring emergencies,
role identification was not consistent
among the various
crews
examined.
Even though the work was
completed
in a timely manner,
there
was
some confusion of
who should perform
a specific duty.
2.2.2
Pro
ram Stren ths
and Weaknesses
~Stnen
the
~
Clear
and consistent briefings
and instructions
by evalu-
, ators were considered
strengths.
~
The facility examines requalification candidates
on
Licensee
Event Report
( LER) based training.
~
The facility training personnel
were very receptive
and
responsive
to examination
comments.
~
The facility personnel
were very responsive
to requests
for
additional
reference materials.
~
The facility Simulator Instructor was very knowledgeable
and versatile with the simulator as well as plant
knowledge.
Written examination
questions
were applicable to an open
reference
examination with few exceptions.
Time validation of the written examinations
was accurate.
e
Weaknesses:
~
Specific weaknesses
with JPMs were identified:
There were
no questions
unique to
SRO levels
It was not apparent that JPMs
and questions
had
been
given
a thorough review by the facility.
This conclu-
sion is based
upon
NRC identification of expected
vs.
given answers,
typographical,
and spelling errors.
Weaknesses
identified in the performance of the
JPMs were
not generally probed
by additional questioning.
The method for identifying and obtaining procedures
at the
start of JPM was not clearly defined
and therefore
not always
consistent.
Examination questions
related to
LERs were not identified
as
such.
One of the Section
A scenarios
had to be substituted
with one of the alternate
scenarios
due to the similarity
(of topics covered) with the other scenario
selected
for
the exam.
There were
some multiple choice questions with no stem
other than
a system category
and choices that were
4
unrelated true/false
statements.
There were
some instances
of distractors
for multiple
choice questions
being obviously incorrect.
Several
short answer questions
had more than
one correct
answer;
the
stem of the question did not contain sufficient
discriminating information.
This weakness
was also identified by the Instructional
Technologist
Group (of the Niagara
Mohawk Training Depart-
ment)
and
had been
addressed
by the facility (see Section
7.2 of this report for further details).
The written examination
questions
were supplied without a
reference
to learning objectives.
The process
of assigning
learning objectives
to
examination
questions is in progress
as part of the
Systems
Approach to Training (SAT) Program.
The written examination
questions
were supplied with only
a K/A value
and not with the K/A number from NUREG 1123.
The facility supplied
a cross
reference
during the onsite
preparation
week which matrixes the facility task number to
the applicable
K/A number.
Incorrect facility task
numbers
were assigned
to
some
questions.
There were
some instances
of questions written on tasks
which were not applicable to the license
held or with
little safety significance'
Note:
The facility resolved
most of the above weaknesses
for
the current examination questions.
To address
these
weaknesses
for the requalification examination
question
bank,
the facility
plans to review the entire bank by October 31,
1990.
3.
Re uglification Pro
ram Evaluation Results
The facility program for licensed operator requalification training met
all criteria established
in ES-601,
"Administration of
NRC
Requalification
Program Evaluation."
Note:
The examination results for the individual who had failed two
previous
NRC requalification examination
and was retested
during this
examination
were not used in the evaluation of the facility
requalification program.
The criteria in ES-601 are:
a.
Ninety percent pass/fail
decision
agreement
between
the
NRC and the
facility grading the written and operating
examinations.
There
was
100Fo agreement
on this criterion.
b.
At least
75/. of all operators
pass
the examination;
not including
individuals selected
who had previously passed
the examination.
NRC grading is the only consideration
for this criterion.
There were
no individuals selected
who had previously passed
the examination.
All operators
(100/) passed
the examination.
c.
There shall
be
no more than
one crew failure during the simulator
portion of the operating
examination,
although the failure of one
crew
MAY cause
the program to be considered
unsatisfactory.
NRC grading is the only consideration
for this criterion.
Three
crews were evaluated
and all three
crews
passed
the simulator portion
of the operating examination.
d.
The program meets
the requirements
of 10 CFR 55.59 (c)(2), (3) and
(4), or is based
on systems
approach
to training.
The review of the licensee's
procedures
for conduct of licensed
operator training indicated that the requalification program meets
the requirements
of 10 CFR 55.59(c)(2), (3),
and (4) for lectures,
on-the-job training,
and evaluations.
In addition,
ES-601 contains criteria that may contribute to a program
being determined unsatisfactory.
None of these criteria were applicable.
4.
Re uglification Examination
Pre aration
The licensee
submitted
reference materials,
test items,
and
a Sampling
plan approximately
60 days before
the examinations
were administered.
These materials
were reviewed in the Regional Office and the specific
test
items proposed
by the facility were reviewed on-site
by the combined
NRC/facility examination
team.
The facility then revised
the items
and
produced
the examination that was administered
to the examinees.
The test
items that were administered
to the operators
are listed in Attachment
2.
The NRC-facility examination
team
spent
a considerable
amount of time in
improving the quality of the simulator scenarios
proposed for the examina-
tion.
Some of unnecessary
operator action evaluation
steps
and Individual
Simulator Critical Task ( ISCT) steps
were deleted
from the scenarios.
The
ISCTs were reviewed against
the "four-fold criteria" in the proposed
Revision
6,
as additional
guidance.
The team's effort in this
area
helped
in identifying valid ISCTs for the examination.
Only minor revisions
were required to the JPMs proposed for the examina-
tion.
The JPMs were generally of good quality.
However,
several
JPN
questions
had to be replaced
because
they were simple "look up" types for
which answers
would be found easily by reading the related procedural
precautions
or steps.
The Sampling
Plan submitted for the examination
was adequate
for the
'urpose.
The plan indicated the emphasis
that each topic received during
the most recent requalification cycle and included
a
summary of the
specific examination
subject requirements.
The written examination questions
submitted for NRC review were generally
satisfactory.
However,
the quality of the questions
could be further
improved
as indicated
by several
weaknesses
identified by the
NRC.
t
F
The facility has
a general
task listing with each task having assigned
a
specific K/A and value.
When
a specific task question
(as
opposed to
a
general
task) is written, the K/A and value assigned
to the general
task
is transferred
to the specific task,
In most instances
the specific tasks
are of a lower safety
importance
than the general
task and the assigned
K/A and value are not applicable.
In fact, there
were several
questions
when compared with the specific item in
NUREG 1123 which did not meet the
3.00 K/A value cut-off criteria for the requalification examinations.
However, the questions
were retained
in the examination to meet the
sampling plan.
guality control
was adequate
for the examination materials that were
submitted to the
NRC following the review by the combined NRC/facility
examination
team.
The facility had
a week to make changes
and review the
corrected materials prior to submittal to the
NRC for final review.
The
examination materials that 'were submitted contained
the specific test
items
and the required revisions that
had been
agreed
upon by the
examination
team.
'j
Refer to Section 2.2.2 for strengths
and weaknesses
identified during the
preparation of the examinations.
5.
Re uglification Examination Administration
The dedication of the facility training personnel
during the extensive
hours that were required for administration of the examinations
was
a
strength of the program.
The stress
of the long hours did not affect the
quality of the evaluations.
Training and operations
personnel
were very
cooperative
throughout the examination
process.
Administration of the examinations
was generally satisfactory.
Time
validation of the static simulator and open reference
examinations
appeared
satisfactory.
The simulator portion of the examination
was conducted
smoothly
and
efficiently.
The scenarios
required minimal setup
time and the simulator
operator did not allow any delays to occur during performance of the
scenarios.
The time of introduction of malfunctions
by the simulator
operator during scenario
was sufficiently flexible and coordinated
by one
facility evaluator to allow all evaluators
to complete all required
evaluations.
The team assessed
the simulator's capabilities
as limited.
The limited
number of malfunctions,
the high dependence
on instructor overrides
( IOs),
and limited number of prepared
scenarios
restricts
the flexibilityof
training and evaluation.
Specific items related
the simulator fidelity
were discussed
with the simulator instructors.
The facility representa-
tives informed the
team that
many
new simulator enhancements
are being
added,
and
a program to write additional
scenarios
has
been established.
The simulator performed well during the examination,
in that there
were
no
delays
due to simulator
down time
The logistics of the walk-through examinations
(JPMs) went smoothly.
The
time validation of the JPMs was reasonably
accurate,
but could be improved
using the data collected during administration of the examination.
Refer to Section 2.2.2 for strengths
and weaknesses
identified'during the
administration of the examination.
6.
Examination Gradin
and Anal sis of Results
Crew performance
on the simulator portion of the examination
was critiqued
by the lead facility examiner
immediately following completion of both
scenarios.
These critiques were satisfactory
and included input from the
licensed operators.
The
NRC and the facility evaluations
discussed
the
results of the'imulator examination
and the followup questions
to be
asked
the examinees
following each individual scenario.
In the majority
of instances,
the
NRC and the facility evaluators
agreed
on all the areas
that were evaluated.
Follow-up questions
were asked
as necessary
to
clarify operator actions.
10
The results of the individual JPMs were discussed
immediately following
administration of the walk-through examinations.
The
NRC and the facility
evaluators
did not agree
on the evaluation of an individual JPM in two
cases
and
an individual
JPM question
in four cases,
but the facility was
more conservative.
A summary of facility grading
on all parts of the examination is included
in Attachment
4 to this report.
Comparison of the
NRC grading
and the
facility gr'ading indicated general
agreement
between
the two.
In general,
the facility grading
was found to be more conservative.
7.
Follow-u
on Previousl
Identified
Re uglification Pro
ram Deficiencies
and Corrective Actions
As
a result of the requalification examination
conducted during the weeks
of July
17 and July 24,
1989,
weaknesses
in the individual operator
performance
and the Nine Mile Point
2 requalification
program were identi-
fied.
The results of the examination
and the weaknesses
were documented
in the examination report 50-410/89-12(OL).
The program was determined to
be unsatisfactory.
Based
on that evaluation,
Nine Mile Point Unit 2
implemented
a Requalification
Program Action Plan to correct
these defi-
ciencies.
The latest revision of the Requalification
Program Action Plan
(Revision 2) was attached
to Niagara
Mohawk's letter
NMP2L 12223 to the
NRC, dated January
10;
1990.
During the week of April 9,
1990,
the
NRC staff reviewed the corrective
actions
implemented
by Niagara
Mohawk to address
the specific issues
addressed
by the Requalification
Program Action Plan.
The results of this
review are
summarized
below.
7. 1
Unsatisfactor
Re uglification Pro
ram
Niagara
Mohawk's corrective actions
in this area listed in the Requal-
ification Program Action Plan are essentially
complete.
The only
corrective action in this area which was
open at the time of this
review was Item
1.BE 10.
This item was subsequently
closed
on April
24,
1990.
This item is related
a follow-up assessment
of the Unit 2
Requalification
program by an Independent
Assessment
Team (IAT).
At
the time of the initial NRC review, the
IAT had just completed their
assessment
and concluded that the Requalification
Program Action Plan
is being implemented
and the original (October 27,
1989)
recommenda-
tions by the
IAT have either been
implemented or are being addressed.
The IAT also concluded that significant improvements
in management
oversight,
operations
and training communication interface,
and
attention to detail
are
now evident,
but continued
management
atten-
tion is needed
in
some areas
to ensure that improvements
are
completed.
Based
on
NRC review of a sample of the completed correct-
ive actions
in this area,
the staff concludes
that the corrective
actions
in this area
are essentially
complete
and significant improve-
ment in the requalification
program is evident.
The observations
by the examination
team in the course of preparation
and conduct of the requalification examination
administered
during
the week of April 30,
1990 support the above conclusion.
Based
on
this evaluation,
Niagara
Mohawk's corrective actions
on this issue
are considered
satisfactory.
7.2
Mritten Examination Structure
Four corrective actions
were identified to satisfy the concerns with
the
1989 written requalification examinations.
These
concerns
were:
1
~
. Test item construction
was not clears
2.
Point values for multiple part answers
were not specified.
3.
Several
double jeopardy questions
were noted
4.
guestions
requiring multiple responses
were not separated
out.
The facility has formally closed out all four of the corrective
actions.
The
NRC'
review of the corrective
action files indicates
that the corrective actions
have
been
completed.
However,
the
NRC's
review of the April 1990 requalification written examinations indi-
cates that
some double jeopardy questions
( Item 3 above)
do exist in
the examination question
bank.
The facility plans to review all bank
questions
by October 31,
1990.
Niagara
Mohawk's corrective actions
and plans to re-review the
exam
bank are considered
satisfactory.
7.3
0 erator
Knowled e Deficiencies
The licensee's
evaluation of the
1989 written examination, raised
concerns
about operator
knowledge deficiencies.
Six corrective
actions
were established
to correct those deficiencies.
The correct-
ive actions for this issue
included:
review of the written examination
results for weaknesses
in the requalification training program,
and
development
and implementation of a remediation
plan.
All corrective actions for this issue
were complete
and found to be
satisfactory
except for corrective action item 3.B.4.6 in the Requal-
ification Program Action Plan.
One licensed operator
had not
completed
the
EOP training required
by this corrective action.
The
NMP-2 training department
planned to train the
one remaining indivi-
dual
by the
end of May 1990.
Successful
completion of training by
the remaining individual will close this issue.
12
completed training in verbal
communications for operators
and
instructors.
Observations
of the operating
crew and training
instructors
are being
made
by the plant management
personnel
during
the simulator training sessions
for identifying and correcting weak-
nesses
in the crew and the instructor performance.
Niagara
Mohawk
has also established
a plan
and
a schedule
to continue
the required
corrective actions
on
an ongoing basis,
for preventing
the recurrence
of identified deficiencies
in this area.
A significant improvement
in verbal
communication skills was noted
during the simulator portion of the April 1990 requalification exami-
nation.
Out of the three
crews
examined,
one crew exhibited excell-
ent communication skills, whereas
performance of the other two crews
was average
and could be further improved.
The corrective actions
in this area which were not fully complete at
the time this inspection
were Items 4.8.3, 4.8.4,
and 4.8.5 involving
crew communications.
Niagara
Mohawk plans to complete
and close out
these
items
by May 14,
1990.
Subject to completion of these
items,
Niagara
Mohawk's corrective actions
on this issue
are considered
satisfactory.
7.5
STA Involvement in Plant Assessment
and Event Control
This issue
deals with clarifying STA responsibilities
(a collateral
reponsibi lity of Assistant Station Shift Superintendent)
during
emergencies
and providing training in this area.
The
STA responsi-
bilities are described
in N2-PDI-1.08, "Operations Policy for Emer-
gency Procedures,"
Revision 3, dated
October
1989.
STAs and instruc-
tors
have
been trained
on these responsibilities.
A program
has
been
established
by the licensee,
and is ongoing, for management
observa-
tion of simulator training.
The
NRC team reviewed the supporting
documentation
and discussed
these activities with Niagara
Mohawk's
personnel.
In addition,
the performance of the
STA in the simulator
during the April 1990 requalification examinations
was observed,
to
identify any weaknesses
associated
with this issue.
No concerns
were
identified.
The Niagara
Mohawk actions
on this issue
are considered
satisfactory.
7.6
0 erator Actions for EOPs
The specific issue
was that operator actions
were not always in
accordance
with the guidance
provided in the
Emergency
Operating
Procedures
(EOPs),
The corrective actions
were reviewed
by the
NRC
team.
No discrepancies
were noted.
Operational directives that establish
management
expectations
have
been
developed
and incorporated
into plant operations
and training.
Management
has also established
a formal review process
in which
management
personnel will observe
simulator training and identify
13
weaknesses
in the crews or training instructors.
The development of
lesson
plans covering Mitigation of Core
Damage is continuing
and
expected
to be completed
by the
end of the year.
The licensee's
corrective actions
on this issue
are considered
satisfactory.
7.7
0 erator
Actions for Normal 0 eratin
Procedures
This issue deals with deficiencies
in operator actions during emer-
gency events
when considering
the requirements
of normal operating
procedures.
The licensee
conducted training in the areas
where
deficiencies
were noted during
EOP refresher training.
The tasks
that operators
were expected
to perform with a procedure
were identi-
fied and training is included in the 1990/1991 Requalification
Program.
The licensee's
document
N2-001-1.09,
"EOP Users Guide,"
defines
management
expectations
for verification of immediate actions
taken during emergency conditions.
The
NRC team reviewed the support-
ing documentation
and discussed
these activities with licensde
personnel.
Also, operator
performance
on the simulator during the
April 1990 Requalification
Examination
was observed
to identify any
weakness
in immediate actions
taken
by the operator s.
No weaknesses
were noted.
This issue is considered satisfactorily resolved.
7.8
D namic Simul,ator Scenarios
The dynamic simulator scenarios
previously used
were not always
realistic,
manageable,
and of approximately
50 minute duration
as set
forth in ES-601.
The corrective actions for this issue
concerning
the quality of the dynamic simulator scenarios
were reviewed.
It was
noted that all but three of the fifteen scenarios
were
one hour in
length vice
50 minutes.
This is,
however, consistent with ES-601
guidelines.
Ten
new scenarios
were to be developed
and incorporated
into the
1990/1991 Requalification
Program.
Nine of the ten were
completed
and
scheduled
in the program.
This issue is considered
satisfactorily resolved.
7.9
Teamwork Durin
Emer enc
Events
The issue
was that teamwork,
including prioritization of crew
actions,
evaluation of plant conditions,
and communications,
was weak
during emergency
events.
The corrective actions for this issue
concerning the weakness
in teamwork, evaluation of plant conditions,
and communications
were reviewed
and the following discrepancy
was
noted.
Item 9.B.3 states
that operator
crews
and training instruct-
ors will be trained to the latest revision of Operation
Department
Instruction, concerning
verbal
communications
and
EOP usage.
This
training was completed;
however, insufficient training records
were
available to show that training was administered
to all personnel
concerned.
The training department
has
made
a commitment to retrain-
ing (by June
30,
1990) in this area to ensure all personnel
have
received this training
(48% completed
as of April 30,
1990).
I
14
Subject to the retraining of all personnel
as discussed
above
and
retention of sufficient training records,
Niagara
Mohawk's corrective
actions
on this issue
are considered
satisfactory.
7. 10 Summar
of Review
The
NRC review of Niagara
Mohawk's actions indicates that the correc-
tive actions
were essentially
complete
and generally effective,
and
that
a significant improvement
in the requalification
program
was
evident.
The
NRC review identified certain
incomplete actions
(see
Sections
7.2, 7.3, 7.4 and 7.9 of this report).
Niagara
Mohawk has
made
a
, commitment to complete
the short term actions
by July 13,
1990,
and
one long term action
by October
31,
1990.
This is an unresolved
item
pending completion of the actions
and their review by
NRC (50-410/
90-16-01).
8.
Assessment
Re ardin
RAP Underl in
Root Causes
2 and
4
Confirmatory Action Letter 88-17, dated July 24,
1988, required Niagara
Mohawk Power Corporation to perform
a root cause
analysis of why they had
not been effective in recognizing
and remedying
problems.
In addition,
Niagara
Mohawk was required
to develop
and implement
a Restart Action Plan
which documented
the underlying root causes
of their management
deficien-
cies
and their associated
corrective actions,
During the weeks of October
9 and
16,
1989,
an Integrated
Assessment
Team
Inspection
( IATI) reviewed the effectiveness
of Niagara
Mohawk's actions
toward resolving the programmatic
and technical
issues
addressed
in their
Restart Action Plan.
The IATI concluded that Niagara
Mohawk's Restart
Action Plan, with respect
to the five identified underlying root causes
was in place
and well understood
by the Nuclear Division personnel;
how-
ever,
the plan was being
implemented with varying degrees
of effectiveness
and performance.
Specifically, the IATI determined that progress
on underlying root causes
(URCs) 1,
3 and 5, (Planning
and Goal Setting, Organizational
Culture,
and
Teamwork, respectively)
showed clear improvement.
For
2 and
4
(Problem Solving and Standards
of Performance/Self-Assessment),
the IATI
concluded that progress
was slow as demonstrated
by limited improvement in
both of these
areas.
Several
team observations
indicated that while
problems
were being identifi'ed, the problems
were frequently not being
resolved.
Further,
although station personnel
were cognizant of the
new
standards
of performance,
their actions did not demonstrate
that they were
incorporating
them into their daily work activities.
During the preparation
and administration of the April 1990 requalifica-
tion examination,
the
NRC team
made the following assessment
of Niagara
Mohawk's performance
under the areas of Problem Solving (URC2) and
15
Standards
of Performance/Self-Assessment
(URC4) with respect
to its
Requalification
Program for licensed operators.
8.1
Problem Solvin
URC2
The
NRC team reviewed the implementation of corrective actions
in the
Niagara
Mohawk's Requalification
Program Action Plan for the deficien-
cies identified during the July 1989 requalification examination.
The team concluded that the corrective
actions
are essentially
complete
and generally effective
and that
a significant improvement
in the requalification program
was evident.
The team also
found that
Niagara
Mohawk has
made
a concerted effort to complete
the required
corrective actions
in a timely manner
and to track the progress
of
these
actions
using its Nuclear Commitment Tracking System
(NCTS).
8.2
Standards
of Performance/Self-Assessment
URC 4
One of the corrective actions
in the Requalification
Program Action
Plan
was to train all operators
and instructors
in verbal
communica-
.
tions during the
Emergency Operating
Procedure
(EOP) simulator
scenario training sessions.
Niagara
Mohawk has completed this
training.
A significant improvement in verbal
communication skills
was noted during the simulator portion of the April 1990 requalifi-
cation examination.
Out of the three
crews examined,
one crew
exhibited excellent communication skills, whereas
the performance of
the other
two crews
was considered
average.
Observations
of the operating
crew and training instructors
are being
made
by the plant management
personnel
during the simulator training
sessions
for identifying and correcting weaknesses
in the crew and
instructor performance.
Niagara
Mohawk has also established
a plan
and
a schedule
to continue
the observations
on an ongoing basis for
preventing
the recurrence
of identified deficiencies
in this area.
The team also noted
good procedural
adherence
by the operators
during
the performance of the simulator
and Job Performance
Measure
(JPM)
portions of the April 1990 Requalification examination.
These observations
were considered
positive indications in the areas
of self-assessment
and implementation of the standards
of perform-
ance.
9.
Follow-u
on Licensee-Identified Violation
The purpose of this section is to document
a licensee identified violation
at Nine Mile Point involving medical
examinations
of licensed operators.
Niagara
Mohawk is committed to Regulatory Guide
(RG) 1. 134,
Rev.
1 (March
1979), for meeting the requirements
needed for medical certification of
its licensed operators
This revision of
RG 1. 134 references
16
ANSI 546-1976,
which is essentially
identical to ANSI 3.4 - 1983.
Regul-
atory Guide 1.134
was revised in April 1987, to reference
the later ANSI
standard;
and,
since then,
Niagara
Mohawk has
used
the
new revision
as
guidance.
The licensee's
previous doctor apparently misinterpreted
the
guidelines
on the
need for laboratory testing
as
a part of the medical
examination.
The misinterpretation
resulted
in
some deficiencies
in
medical
examinations;
namely,
laboratory work was not done.
The Certi-
fication of Medical Examination
(NRC Form 396) states
that the guidance
in
was followed; and,
as
such,
a licensee
representative
certi-
fies,
by signature,
that the information
on the
Form 396 is true
and
correct.
Section
50.9 of
10 CFR Part 50 states,
in part, that information provided
to the Commission
by a licensee
shall
be complete
and accurate
in all
material
respects.
Contrary to the above,
not all medical
examinations
were complete
and accurate.
This is
a Severity
Level
IV violation.
In reviewing this matter,
the
NRC staff has determined that issuing
a
Notice of Violation (NOV) is not appropriate.
The staff has
chosen to
exercise discretion
because
the violation meets all of the criteria of
Appendix
C of 10 CFR Part 2, Section
G as discussed
below.
1.
The violation was identified by the licensee.
They discovered
the
inaccuracies
during discussions
between their physician
and the
license holders.
2.
The violation is normally classified at Severity Level
IV or V.
This
is
a Level IV.
3.
The violation was reported.
The licensee
telephoned
the Region I
office and followed this up with a letter to the Region (Attachment
5 to this report) documenting
the issues.
4.
The violation has
been corrected.
As stated in a letter. dated
March
12,
1990,
from Niagara
Mohawk to the Regional Administrator, all
licensed operators
have
been
re-examined
using the guidance of ANSI/
ANS 3.4-1983
(see Attachment
6 of this report).
It is expected that
future medical certifications will continue to be accurate.
5.
The violation was not willful nor could it have
been prevented
by
corrective action for a previous 'violation.
There are
no indications
of any deliberate falsification of documents
nor are there
any indi-
cations that the licensee
was reluctant to promptly notify the Region
once the errors
were discovered.
Furthermore,
these errors were the
result of one doctor's interpretation of the guidance.
In summary,
the
NRC staff has determined that enforcement discretion is
the correct response
to this matter
and that
no further action is
necessary.
17
10.
~Ei
I
An exit meeting
was held at the conclusion of the examinations
on
May 4,
1990.
The personnel
in attendance
are indicated in Attachment
1.
The
preliminary
NRC results of the simulator
and walk-through portions of the
examinations
were presented.
Examination preparation
and administration
were discussed
along with the results of the facility administered
exami-
nations.
Attachments:
1.
Persons
Contacted
2.
Requalification
Examination Test Items
3.
Documents
Reviewed
4.
Licensee
Results,
Licensee's
Letter to NRC, dated
May 18,
1990
5.
Licensee's
Letter to
NRC, dated
February
21,
1990
6.
Licensee's
Letter to
NRC, dated
March 12,
1990
V
jl
Attachment
1
Persons
Contacted
1.
Nia ara
Mohawk Power Cor oration
R. Abbott, Station Superintendent
(2)
W. Bandla, Unit
1 Asst.
Supdt.
Operations
(2)
RE
Brown, Instructor
( 1), (2), (4)
G. Brownell, Nuclear Regulatory
Compliance (2)
S. Burton, Unit
1 Requalification Training (2)
G. Brownell, Nuclear Regulator
Compliance
( 1)
J.
Cobb, Facility Evaluator (2) (4)
M. Colomb, Operations
Superintendent
( 1), (2), (4)
G. Corbin, Supervisor Simulator Tech. (1), (2)
B. Hennigan,
Instructor (1), (2), (3)
J.
Kaminski, Unit
1 Operations
Training (2)
J. Pointexter,
Training Supervisor (1)
A. Rivers, Superintendent
Training Nuclear (2)
R. Seifried, Asst.
Supdt. Training ( 1) (2)
J.
Throckmorton, Facility Evaluator (2), (4)
J. Toothaker, Facility Evaluator (2), (4)
E. Townsent,
Operations,
(2) (3)
P. Walsh, Facility Evaluator (2), (4)
B. Williamson, Facility Evalvator (2), (4)
2.
Nuclear
Re viator
Commission
NRC
P: Bonnett,
Operations
Engineer
( 1), (2)
G. Buckley,
Examiner (PNL) (2)
L. Larson,
Examiner
(PNL) (2)
R.
Laura,
Resident
Inspector (2)
S. Pullani, Senior Operations
Engineer (1), (2)
J. Williams, Senior Operations
Engineer (1), (2)
Notes
(1) Attended Entrance
Meeting, April 9,
1990
(2) Attended Exit Meeting,
May 4,
1990
(3) Member,
Combined Facility/NRC Examination
Team
(4) Facility Evaluator
Attachment
2
Re uglification Examination Test Items
!
~ ~
~ ~
0
~ I
j
SIMULATOR SCENARIOS
SIMULATOR EXAM 51
SCENARIO
SCENARIO
SIMULATOR EXAM 52
02-REQ-009-1DY-2-14
02-REQ-009-1DY-2-15
SCENARIO
SCENARIO
SIMULATOR EXAM 53
02-REQ-009-1DY-2-14
02-REQ-009-1DY-2-15
SCENARIO
SCENARIO
02-REQ-009-1DY-2-14
02-REQ-009-1DY-2-15
JPM'S
EXAM I1
COMMON
02-REQ-SJE-264-2-44
02-REQ-SJE-200-2-55
02-REQ-SJE-200-2-10
02-REQ-PJE-262-2-66
02-REQ-PJE-296-2-74
UNCOMMOM
EXAM I2
EXAM I3
02-REQ-SJE-259-2-46
02-REQ-SJE-203-2-48
02-REQ-SJE-206-2-58
02-REQ-PJE-200-2-63
02-REQ-PJE-264-2-65
COMMON
02-REQ-SJE-264-2-44
02-REQ-SJE-200-2-55
02-REQ-SJE-200-2-10
02-REQ-PJE-262-2-66
02-REQ-PJE-296-2-74
UNCOMMON
02-REQ-SJE-261-2-38
02-REQ-SJE-201-2-40
02-REQ-SJE-200-2-53
02-REQ-PJE-296-2-83
02-REQ-PJE-200-2-69
COMMON
02-REQ-SJE-264-2-44
02-REQ-SJE-200-2-55
02-REQ-SJE-200-2-10
02-REQ-PJE-262-2-66
02-REQ-PJE-296-2-74
UNCOMMON
02-REQ-SJE-205-2-8
02-REQ-SJE-253-2-24
02-REQ-SJE-200-2-50
02-REQ-PJE-296-2-86
02-REQ-PJE-200-2-71
WRITTEN EXAM RO-1
A1 02-REQ-009-1ST-2-29
S04
S05
S06
S07
S08
S10
S11
S12
S13
A2 02-REQ-009-1ST-2-36
S03
S04
S05
S06
S07
S08
S09
S10
S11
S12
2000110501-B01
2000200501-B02
2000270501-B03
2000400501-B01
2009230501-B01
2010100101-B01
2019230101-B01
2020060101-B01
2020060101-B02
2040010101-B01
2049110101-B01
2059330101-B01
2119090401-B01
2150230101-B03
2189030401-B01
2239220101-B01
2490020101-B01
2539060401-B05
2569090401-B01
2619010101-B01
2889230101-B02
~ I
WRITTEN EXAM RO-2
A1 02-REQ-009-1ST-2-22
S04
S05
S06
S07
S08
S09
S10
B1
02-REQ-0090-1ST-2-40
S03
S04
S05
S06
S07
S08
S09
S10
2000130501-B01
2000310501-B01
2000690501-B01
2009230501-B01
2010080101-B01
2010130101-B01
2029180101-B01
2029360101-B01
2059300101-B01
2090040101-B01
2119010401-B01
2119170101-B01
2150230101-B01
2230220101-B02
2439070101-B03
2490020101-B02
2539060401-B03
2740050101-B01
2769100401-B02
2889390101-B01
2949040401-B01
2969010101-B01
VRITTEN EXAM RO-3
A1 02-REQ-009-1ST-2-30
S02
S03
S04
S05
S06
S07
S08
S09
S10
S11
A2 - 02-REQ-009-1ST-2-35
S03
S04
S05
S06
S07
S08
S09
S10
S11
S12
2000020501-B01
2000160501-B01
2000310501-B01
2000400501-B01
2000690501-B02
2009230501-B01
2020060101-B03
2059330101-B01
2059380101-B01
2089130401-B01
2110040101-B03
2119090401-B01
2150220101-B01
2189120601-B01
2230020101-B01
2399150401-B01
2549010401-B01
2760040101-B01
2850070101-B01
2889040101-B03
2949010101-B01
VRITTEN EXAM SRO-1
A1 02-REQ-009-1ST-2-29
S02
S03
S04
S06
S07
S08
S10
S11
S13
A2 02-REO-009-1ST-2-36
S01
S02
S03
S04
S06
S07
S08
S09
S11
S12
2000200501-B02
2000270501-B02
2009230501-B01
2010100101-B01
2019230101-B01
2020060101-B01
2020060101-B02
2040010101-B01
2049110101-B01
2119090401-B01
2150230101-B03
2189030401-B01
2539060401-B05
2569090401-B01
2889230101-B02
3410180303-B03
3410180303-B09
3440390303-B02
3449400603-B01
3449560603-B02
3450420503-B03
WRITTEN EXAM SRO-2
A1 02-REQ-009-1ST-2-22
S01
S03
S05
S07
S08
S09
S10
A2
02-REQ-009-1ST-2-40
S01
S02
S03
S05
S06
S07
S08
S10
2000400501-B01
2009230501-B01
2010080101-B01
2029180101-B01
2029360101-B01
2059330101-B01
2090040101-B01
2119010401-B01
2119170101-B01
2150230101-B01
2230220101-B02
2439070101-B03
2539060401-B03
2740050101-B01
2769100401-B02
2889390101-B01
2949040401-B01
2969010101-B01
3410330303-B01
3440150303-B01
3440170303-,B01
3440310303-B04
VRITTEN EXAM RO-3
A1 02-REQ-009-1ST-2-30
S01
S02
S03
S04
S05
S06
S07
S08
S09
S11
A2 02-REQ-009-1ST-2-35
S01
S02
S03
S04
S05
S06
S08
S09
S10
S12
B
2000020501-B01
2000160501-B01
2000310501-B02
2000400501-B01
2010170101-B01
2019100401-B01
2020060101-B03
2059330101-B01
2089130401-B01
2150220101-B01
2230020101-B01
2399150401-B01
2549010401-B01
2760040101-B01
2889040101-B03
3410180303-B04
3410180303-B10
3449390603-B02
3449410603-B01
3449530603-B01
3450420503-B01
Attachment
3
Documents
Reviewed
Number
NTP-11
OPS/2070
NMP-63431
OPS/2067
02-REQ-001-221-2-01
02-REQ-0009-TRA-2-01
Title
Licensed Operator Requalification Training
Licensed Operator Requalification Training
Biennial Schedule
90/91
Memo.
from A. Rivers to J. Willis;
March 21,
1990;
Subject:
NMP-2 Requalification Training
Cycle Status
Report through Cycle 2, 90/91
Licensed Operator Requalification Training
Cycle
C02 90/91
Schedule
(Feb.
5,
1990-
March 9,
1990)
Containment
Entry and Exit (Lesson
Plan)
Loss of Electrical
Power/Loss of SSW
(Simulator
Lesson
Plan)
Selected
training records
Revision
2
NA
NA
Oec.
89
NA
Attachment
4
~
Licensee
Results
7 NIAGARA
u MOHAWK
NHP-67414
NINE MILE POINT NUCLEAR STATION/P.O. BOX 32 LYCOMING,NEW YORK !3093/TELEPHONE (315) 343-2110
May 18, .1990
Mr. Timothy Martin
Regional Administrator
ATTN: Mr. Robert
M. Gallo
Branch Chief
United States
Nuclear Regulatory
Commission
Region
I
475 Allendale
Road
King of Prussia,
19406
Oear
Mr. Martin
Attached
are
the
Facility
grades
for
the
NRC
evaluated
Operator
Requalification
Examinations
administered
at
Niagara
Mohawk
Power
Corporation,
Nine Mile Point
Unit
2 during
the
week
oF April 30,
1990.
A
summary
of
our
results
as
compared
to the
program evaluation criteria
oF
and
a
selF
evaluation
of
our
Licensed
Operator
Requalification
Program
are
also
included.
Please
Feel
Free
to contact
me if any
Further
information is desired.
Thank
you
For your cooperation
and the cooperation
of your stafF.
Sincerely,
~nEc'..
J.
L. Willis
General
Superintendent-Nuclear
Generation
JL'A/v'GP/kab
Attachments
cc:
S. Pullani
(USNRC)
LICENSED OPERATOR
REQUAL PROGRAM
SELF-EVALUATION
Executive
Summary
During the
week of April 30,
1990,
NRC administered
Requal
Exams
were
given at Nine Mile Point Unit 2.
Fifteen individuals comprising three
control
room teams
were examined.
Results
are
as follows:
All three control
room
teams
were satisfactory.
Six of six
passed
the simulator
exam.
Nine of nine
ROs passed
the simulator
exam.
All fifteen operators
passed
the walkthrough
exam.
All fifteen operators
passed
the written exam.
All Program Evaluation Criteria that
can
be evaluated
by the facility
were satisfied.
More emphasis
is needed
on communications
during normal operations.
The
exam bank needs
to be
improved
in several
areas.
The program
has
shown significant
improvement
since
the
1989
exam
failure.
NRCU2/408
-1
May 1990
1.0
EXAM RESULTS
1.1
Individual
Exam Results
Note:
Fifteen operators
took the
exam.
Only fourteen
are
counted
for the program evaluation
since
one operator
was
a "retake"
candidate.
Pass/Fail
Pass/Fail
TOTAL
Pass/Fail
WRITTEN
SIMULATOR
WALKTHROUGH
OVERALL
8/0
8/0
8/0
8/0
6/0
6/0
6/0
6/0
14/0
14/0
14/0
14/0
A more detailed
summary
by candidate
is attached.
Attachment
1 gives
the
grades for each
section of the
exam by candidate.
Attachment
2 is
a
matrix showing all
exam
items given to each
candidate.
1.2
Generic
Strengths
and
Weaknesses
Strengths
Use of Operating
Procedures
SSS control of the shift
Recognition or off normal
events prior to alarm
Alarm response
was timely with good action
Overall operator
task performance
Weaknesses
Communications
during normal operations
could
be
improved.
SSS did not always
inrorm the control
room shift of equipment
which had
been
"ec ared inoperable
Operators
did not always
ensure
that the
acknowledged
reports
had to ask for a parameter
and
then the parameter
trend
during emergency
events
Roles
are noi always clearly demonstrated
during emergencies
2.0 Program Evaluation
The Nine Mile Point Unit 2 Requal
Program
meets
the cri teria of ES-601
Rev.
5 as follows:
-2
May 1990
NRCU2/408
2.1
100'/. of the operators
passed
the
exam.
This exceeds
the
75'/
requirement of C.3.b.(1)(b).
2.2
The program meets
the requirements
of 10-CFR-55.59 (c)(2),(3)
and (4).
C.3.b. (1)(d)
2.3
One
common
JPM was failed by two of the fourteen operators. 'o other
common
JPM was failed by more
than
one operator.
This satisfies
the
criteria of C.3.b(2)(a).
2.4
No common
JPM question
was missed
by more than
one operator.
This
satisfies
the criteria of C.3.b(2)(b).
2.5
and
were rotated into all the licensed positions
they would
be expected
to fulfill at Nine Mile Point Unit 2.
This satisfies
the
criteria C.3.b.(2)(c).
2.6
Operators
were trained for in plant
JPMs satisfying
the criteria of
C.3.b.(2)(d).
2.7
100/ of the operators
answered
at least
80'/ of their
common
questions
correctly satisfying
the criteria of C.3,b.(2)(e).
2.8
A11 control
room crews
were satisfactory,
satisfying
the requirements
or O.l.c.(2)(c)4.
2.9
All operators
passed
the walkthrough
.exam satisfying
the requirement
of 0.2.c.(2)(b)(2).
2.10 All operators
passed
the written exam, satisfying
the -requirements
of
0.3.c.(2)(b).
3.0 Lessons
Learned
3.1
Exam Preparation
The following items
became
apparent
during the
exam process.
They
will be corrected
in preparing for our next exam.
The formality of exam preparation
needs
to improve.
Documentation
or the steps
in the process
needs
to be developed
and retained.
Exam questions
prepared
from industry events
need to reference
the event.
Job Performance
Measures
need questions
written to a higher
cognitive level.
Job Performance
Measures
need questions
unique to the
candidate.
NRCU2/408
Job Performance
Measures
could have
more than
two questions
to
allow evaluators
more flexibility.
-3
May 1990
/
More Limits and Control questions
on
need to be developed
to match
the
sample
plan.
An exam bank review for double jeopardy
and direct lookup
questions
needs
to be done.
3.2
Plant Operations
Normal plant operation
communications will continue
to be
stressed
in training.
Operator roles during emergency
situations will continue
to be
stressed
in training.
Reporting parameters
and
the trends will continue to be stressed
in training.
Note:
Operating
Department Instructions
and recently revised
Nuclear
Training Instructions
provide
the necessary
guidance
to address
the areas
for improvement
noted
above
and will continue
to be
emphasized
during training.
NRCU2/408
-4
May 1990
POHI:R
PLANT RLQUALII'ICATIONRLSlILIS SUIIHARY SIIL'FT
Name
Candidate
1
Candidate
2
Candidate
3
Candidate
4
Candidate
5
Candidate
6
Candidate
7
Hri t ten
Score
100
94.9
06.7
92.0
90.
1
JPHs
"/
100
100
90
100
80
100
90
Quest.
100
100
100
100
90
90
S imul .
P/F
Results
Hritten/0 eratin
P
/
P
P
/
P
P
/
p
P
-/
p
P
/
p
P
/
p
P
/
p
NRCU2/408
-6
Hay
1990
POHER
PLAHT REQUALIFICATION RESULTS
SUIIMARY SIIEET
Hame
Candidate
8
Candidate
9
Candidate
10
Candidate ll
Candidate
12
Candidate
13
Candidate
14
Candidate
15
Imari
t ten
Score.
94,5
94
5
100
100
100
100
100
100
JPI Is
"/
IOO
90
I 00
90
100
100
100
100
Quest.
95
100
90
100
100
100
100
S imu1 .
P/F
Resul ts
Nri tten/0 eratin
P
/
P
P
/
P
P
/
P
P
/
P
P
/
P
P
/
P
P
/
P
P
/
P
y
',h
~
h
~ '
HRCU2/408
-5
I"lay I')90
Attachment
5
Licensee's
Letter to
NRC
dated
Februar
21
1990
NINE MILEPO(NT NUCLEARSTATION/I .0, BOX 32. LYCQMING.N Y. I30'33IIELI Pl >ONE (315) 343 <>I IP
February 2l,
1990
Hr. William T. Russell
Regional Adminis t:ra toe.
475 Allendale
Road
King of Prussia,
PA 19406
Ri:
>e H- '
Poii>t Nuc'ar Stati<>n Unit i and Uni t
2
Docket Nos. 50-220/50-410
Dear Sir-
The Niagara
Mohawk Power Corporation is submitting this letter as
a follow-up
to a recent conversation with Region I concerning
a deficiency in the medical
examiiiations received
by Nine Mile Point Nuclear Station Licensed Operators-
As a resul.t of a recent
review of our proceduees, it was determined
that
required laboratoey
tests
have not been rout.i<<ely performed.
As a matter of bacl'ground,
in order to meet
the requirements
oF Part 55,
NHPC
For Nine Mile Point Unit 2, committed in the
FSAR, Table 1.8-1 to follow
Rev.
1 (March 1979) and ANSI N546-1976.
No such
commitment
was
made for Unit 1, although it is, of course,
our practice
to
fol.low tlie same
procedures.
In April 1987,
the Nucl'ear Regulatory
Coi>missio<<
piiblished Regulatory
Guide 1.134,
Rev.
2, "Medical Evaluation of Licensed
I'eesonnel for Nuclear
Power Plants" endorsing
the American National Standard
ANSI/AN1-3.4-1983, 'edical Certification and Honitoring of Personnel
Requieing Operator Licenses for Nuclear Po~er Plants"
as
an acceptable
method
for determining medical qualification of applicants for initial or renewal of
Ope!;a I < ~ >
ne SeniOr
Onera t:Or
1 renaeS.
Niagara
HOl>aWlt USed
tl>o. pew ANST
standards
as guidance for medical examinations for licensed operators
~
l.'hysical examinations
are performed by a doctor under contract to NHPC.
After
I:he effective date of the new rule on operator licensing,
NHPC contiiiued to
use
NRC Form 396 (7-81) for documenting medical history by the candidate
and
physical data recorded
by the examining physician.
Completed
Forms
396 (7-8l)
were
used
as objective evidence of completion of physical examinations
and as
Llie basis
to certify the candidates
medical status
on the
NRC Form 396 (l0-86,
ltJ-88 aud
10-89) submitted
to the
NRC as part of tlie licensiiig or rei>ewal
app1 ica t i.on.
I.'rca>Ise of t:lie eecei>t
implementation nf tl>e Fitiiess for D<<ty rule,
NHPC
ret:i,iii~d Lli
seevi<:es
of a phvsicia<<at
our Ni<<e Hi.le Point Nuclear Stat:ioii.
'I'lii.s pliysi<. iaii was
asked
to dete>w>ine whetlier: oe <<ot.'ie
coul.d
peeforn>
,l.ice<<sii>g
pl>ys ical s hare.
During his evaluat:ion of
t lie requirements
the
l>liysiciaii reviewed
Discussions
beLwee>>
tl>is physiciai> a<<d
I I,<<.. Iii.>r. t>oldri;s
1r<l
Lo t:lie findi>>g that: tlie laliorato>'y worl; lia<l i>ot.'eeii
p<.>:lu>!<<><!<J iii Llie l>tist. ~
Discussions witli tlie previous
l>liysici:>>i co<<fi>>>>r<l I.liis
I:<<:t .
I':gp,i
I'ir. Wi,l I inm T. IIussel
I
I'eI> runty
21,
1990
I<'LII'Q AC'1~IVi
As discussed
with the
NRC, in order to reconfirm the individual certification
of licensed operators,
NIIPC is reexamining all license holders in accordance
with ANSI/ANS 3.4-1983.
The examinations
are expected
to be completed
by
February
23,
1990, with results of the laboratory tests
received
and reviewed
by Narch
1,
1990.
At the conclusion,
NMPC will submit, by letter,
certification that the guidance
contained in ANSI/ANS 3.4-1983
was followed
and a determination
as to whether
each license holder's physical condition and
general health is such that it would not cause operational errors endangering
public health
and safety.
J.. Willis
General
Superintendent-Nuclear
Generation
JLW/lmc
(131<V)
Attachment
6
Licensee's
Letter to
NRC
dated
March
12
1990
4~
~<~<
<<~L< >OINT NUCLEAR STATIQN <g (J
- ~>
~ '"~Q
~ )
~ '"
~ '~ )"'
) )
~
'arch
12,
1990
Hr. William Russell
Regional Administrator
ATTN:
Mr. Robert
M. Gallo
Branch Chief
United States
Nuclear Regulatory
Commission
Region I
475 Allendale Road
King of Prussia,
19406
RE:
Nine Mile Point Nuclear Station Unit 1 and Unit 2 Docket
u~50 220/50
410
Dear Hr. Russell:
Niagara
Mohawk
Power
Corporation
hereby
reports
completion of the
Operator physical'xaminations
described
in our letter of February
21,
1990.
A copy of this letter is included for your reference.
A medical examination
was conducted for each Licensed Operator at Nine
Mile Point Nuclear Station Unit
1
and Unit
2 in accordance
with the
guidance
contained in ANSI/ANS 3.4-1983.
Based
on the results of the examinations,
the physician has determined
that the physical condition and general health of the licensed operators
at
Nine Mile Point Units
1
and
2 are
not
such that
they might cause
operational errors endangering
public health
and safety except
as noted
below.
Fou
license holders require
amendments
to their "Ce ti ication of
Med'cal Examination by Facility Licensee
(NRC Form 396)" due to changes
in medical history.
Notification in accordance with 10CFR55.25 for these
individuals is being sent to you under separate
cover.
Sincerely,
General Superintendent
Nuclear Generation
JLW/lac
Attachment